An Efficient Nodal Method for Transient Calculations in Light Water Reactors
Author:
Affiliation:
1. Korea Atomic Energy Research Institute P.O. Box 7, Daeduk-danji, Taejon, 305-606, Korea
2. Hanyang University Department of Nuclear Engineering, Seoul, 133-791, Korea
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT93-A34840
Reference16 articles.
1. Coarse-Mesh Flux-Expansion Method for the Analysis of Space-Time Effects in Large Light Water Reactor Cores
2. R. A. SHOBER, “A Nodal Method for Solving Transient Fewgroup Neutron Diffusion Equations,” ANL-78-51, Argonne National Laboratory (June 1978).
3. K. S. SMITH, “An Analytic Nodal Method for Solving the Two-Group, Multidimensional, Static and Transient Neutron Diffusion Equations,” MS Thesis, Massachusetts Institute of Technology (Mar. 1979).
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